ITER divertor heat transfer system and loss of vacuum accident sequence analyses overview

• Published in: Fusion Engineering and Design Vol. 42; no. 1; pp. 95 - 101
• Main Authors: Cambi, G., Porfiri, M.T., Jahn, H., Cepraga, D.G., Bartels, H.-W.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 03.09.1998; New York, NY Elsevier Science
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Installations for energy generation and conversion: thermal and electrical energy; Nuclear safety; Tokamak; Nuclear fusion reactor; LOCA; Vacuum; Divertor; Leak; Thermohydraulics; Heat transfer
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/S0920-3796(98)00090-8

The paper presents the analyses performed by the European Union ITER Home Team for five ITER reference accident sequences: two loss of flow and two loss of coolant accidents on the divertor primary heat transfer system, and one loss of vacuum accident. Tritium and activated materials ground and stack environmental releases have been evaluated for each one of the accident sequences, up to 7 days from the accident start. The ATHENA and the INTRA codes are used for the accident transient thermal–hydraulic analysis and for the containment response to coolant leaks, respectively. The NAUA Mod 5M code has been used to assess the radioactive material transport, deposition and leakage inside and through the containment.